US6047037A - Multi-lift tool and method for moving control rods in a nuclear reactor - Google Patents
Multi-lift tool and method for moving control rods in a nuclear reactor Download PDFInfo
- Publication number
- US6047037A US6047037A US08/871,031 US87103197A US6047037A US 6047037 A US6047037 A US 6047037A US 87103197 A US87103197 A US 87103197A US 6047037 A US6047037 A US 6047037A
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- United States
- Prior art keywords
- control rod
- grapple
- frame
- support piece
- fuel support
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- Expired - Lifetime
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates generally to tools for use in nuclear reactor facilities and, in particular, to a tool and method for exchanging and shuffling control rods in a boiling water nuclear reactor.
- control rods are used to control the reactivity and power output of fuel assemblies.
- the control rods are used to shut down the reactor and compensate for long term reactivity changes associated with uranium depletion and fission product buildup.
- the control rods also function to control the power distribution among fuel assemblies.
- the control rods enter the core of the reactor vessel from the bottom, and their presence in the lower portion of the core helps to balance the reactivity effects of steam voids in the upper portion of the core and thus tends to flatten the axial power distribution.
- the basic design of the BWR control rod assembly is shown in FIG. 1.
- the control rod assembly 20 consists of a cruciform-shaped stainless steel sheath 21 enclosing eighteen to twenty-one absorber rods 22 in each of its four wings.
- the absorber rods 22 are stainless steel tubes filled with boron carbide powder (B 4 C) compacted to approximately 65% of theoretical density in which the B 10 isotope is the primary neutron absorber.
- B 4 C boron carbide powder
- the tubes are seal-welded with end plugs on either end.
- the individual tubes act as pressure vessels to contain the helium gas released by the boron-neutron capture reaction.
- a control cell in which the control rod 22 is positioned is shown schematically in FIGS. 2a-c and 3.
- the control cell includes a control rod guide tube 24, a fuel support piece 25, and fuel assemblies 26.
- a plurality of the control rod guide tubes 24 are inserted into holes arranged in a grid in the lower core plate 27. Each guide tube 24 is oriented by alignment lugs 28 which fit over the anti-rotation pin 29 in the lower core plate 27.
- the control rod drive 30 penetrates the reactor pressure vessel bottom head and is latched to a coupling 31 on the lower end of the guide tube 24.
- the control rod drive piston 32 enters the lower end of the guide tube 24 and is coupled to the control rod 20 with a spud mechanism 33.
- a velocity limiter 34 is formed at the lower end of the control rod 20. Guide rollers 35 on the velocity limiter 34 bear on the inside wall of the guide tube 24 to give lateral support for the control rod 20.
- the fuel support piece 25 rests in the top end of the guide tube 24.
- the fuel support piece 25 is supported by a 45 degree sealing ring on the top inside diameter of the guide tube 24.
- the orientation of the fuel support piece 25 is maintained by alignment lugs 28 on one corner which engage the anti-rotation pin 29 in the lower core plate 27.
- the fuel support piece 25 is cylindrical at its lower end to fit into the guide tube 24.
- the upper portion of the fuel support piece 25 consists of four lobes which hold the four fuel assemblies 26 of the control cell. Beneath the hole in the upper surface of each lobe is a cast-in flow path which directs coolant flow into the fuel assembly 26.
- the coolant flow enters through orifices 36 in the outside diameter of the lower portion of the fuel support piece 25, which are aligned with holes in the control rod guide tube 24.
- the fuel support pieces 25 for peripheral control cells have smaller orifices 36 for the fuel bundle positions that are on the outer row of fuel. This orificing arrangement makes the peripheral fuel support pieces 25 unique to their location so that they cannot be moved from place to place during control rod change operations.
- the control rod 20 passes through a cross-shaped hole 37 in the fuel support piece 25.
- a neutron source 38 which occupies a blind corner hole and a bypass flow plug 39 positioned in a through hole adjacent to the fuel support piece 25.
- the four fuel assemblies 26 of the control cell are supported by the lobes of the fuel support piece 25 and occupy the corners of the cell leaving a cross-shaped space at the center for the control rod 20.
- the rollers 35 on the tip of the control rod 20 contact the outer surface of the fuel assembly channel to provide lateral support for the control rod 20 when it is inserted.
- control rod 20 In order to replace a control rod 20 according to the conventional procedure, the fuel assemblies 26 and the fuel support piece 25 in its control cell must be removed. The control rod 20 can then be uncoupled from the drive mechanism 30 and removed from above the reactor.
- control rods 20 require that the rods be replaced on a regular basis.
- some plants have found it advantageous to extend the life of the control rods 20 by shuffling the control rods 20 between high and low exposure locations in the core in order to equalize the exposure over a larger number of rods.
- Some reactors have adopted a particular fuel loading scheme, which concentrates the exposure on one group of control rods 20 (e.g., 1/6 of the total number of rods) while keeping the remainder of the control rods in a fully withdrawn position. This loading scheme requires more frequent control rod shuffles in order to equalize exposure among the blades of the control rods.
- Movements of fuel assemblies 26, control rods 20, and associated components are accomplished through use of a refueling platform or bridge and its associated hoisting equipment.
- a conventional arrangement is shown in FIGS. 4a and 4b.
- the refueling platform 40 spans the reactor vessel 41 and the reactor cavity 42 and the fuel pool 43.
- the refueling platform 40 is supported at its ends by respective A-frame supports 44 which run on tracks 45 embedded in the floor.
- a trolley 46 runs across the platform 40 on its upper structure at a level several feet above the tracks 45.
- a first main hoist 46a is supported by the trolley 46 and has a lift cable 47a extending therefrom for raising and lowering the fuel assemblies 26 or a blade guide 49, for example.
- a second hoist 46b is mounted to the frame of the trolley 46 and has a lift cable 47b for raising and lowering the fuel support piece 25, for example.
- a third hoist 46c is mounted to a monorail extending along the platform 40 and has a lift cable 47c for raising and lowering the control rod 20, for example.
- the platform 40 and trolley 46 are designed to transport fuel assemblies 26, control rods 20, blade guides 49, fuel support pieces 25, and other contaminated components under water between various points in the reactor cavity 41 and the reactor vessel 42, or between the reactor and the spent fuel pool 43.
- a suitable grapple 50a, 50b, 50c is secured to the lower end of each of the lift cables 47a, 47b, 47c, respectively, for attaching the lift cables to the components to be lifted.
- FIGS. 4a-b and 5 of the drawings A typical sequence of moves involved in changing a control rod 20 using conventional tools will now be described with reference to FIGS. 4a-b and 5 of the drawings.
- two diagonally opposed fuel assemblies 26 are removed one at a time from the control cell using a main grapple 50a supported by the lift cable 47a of the main hoist 46a and transported to storage in the spent fuel pool 43, to an in-vessel storage rack 48, or to another core location as part of a fuel shuffle.
- a blade guide 49 is transported on the main grapple 50a of the lift cable 47a from a storage location and inserted into the open holes of the control cell left by the removed fuel assemblies 26.
- the remaining two fuel assemblies 26 are then removed one at a time from the control cell using the main grapple 50a and hoist 46a and are stored in the fuel pool 43 or other suitable location.
- control rod 20 is then fully withdrawn from the cell using the control rod drive mechanism 30, and the drive is then valved out of operation.
- the blade guide 49 is then removed from the control cell using the main grapple 50a and hoist 46a and taken to a storage location or left hanging from the lift cable 47a. This is represented by step (a) in FIG. 5.
- a fuel support grapple 50b and grid guide are then installed on the lift cable 47b extending from the second hoist 46b.
- the arms of the grapple 50b are closed to allow the grapple 50b to pass through the top grid 51.
- the grapple arms are released and the grapple 50b is lowered onto the fuel support piece 25.
- the grapple 50b closes on the fuel support piece 25 and is then lifted free of the control rod guide tube 24 with the second hoist 46b.
- the fuel support piece 25 is then raised up through the top grid 51 and left suspended from the lift cable 47b of the second hoist 46b. This is represented by step (b) in FIG. 5.
- control rod 20 is then unlatched from the control rod drive 30 and removed using a control rod latch tool (not shown) supported by the third hoist 46c.
- a grid guide may be used with the latch tool.
- the control rod latch tool is lowered onto the top handle 52 of the control rod 20 with its lower section resting in the angle between two of the wings of the control rod 20.
- step (c) in FIG. 5 When the latch tool is fully seated on the control rod 20, actuation of the tool with the engage button on the hoist pendant causes the lifting hook to engage the top handle 52 of the control rod 20 and the actuator hook in the lower end of the tool to engage and lift the unlatching handle 53 of the control rod 20, thus releasing the control rod 20 from the control rod drive 30.
- the control rod 20 is then lifted out of the guide tube 24 with the latch tool.
- the position of the control rod drive 30 is monitored to verify that the control rod 20 has been successfully unlatched from the drive.
- the control rod 20 is then transported to the fuel storage pool 43 and placed in a storage rack 54. This is represented by step (c) in FIG. 5.
- a new control rod 20 is then transported from the pool 43 with the control rod grapple 50c suspended from the third hoist 46c. This is represented by step (d) in FIG. 5.
- the new control rod 20 is placed in the control rod guide tube 24 and lowered to rest on the bottom of the guide tube 24. Coupling of the control rod 20 to the drive 30 is usually deferred until after the fuel support piece 25 and blade guide 49 have been inserted into the cell.
- step (e) in FIG. 5 The fuel support piece 25 is then lowered into the control cell and over the top of the control rod 20 until it is seated in the top of the guide tube 24. This is represented by step (e) in FIG. 5.
- step (e) in FIG. 5 When the fuel support piece 25 is installed in the proper orientation, the grapple arms are released and the grapple 50b is lifted off of the fuel support piece 25.
- the blade guide 49 is then installed in the control cell from its hanging position or its storage position. This is represented by step (f) in FIG. 5.
- the control rod 20 is then recoupled by moving the piston 32 of the control rod drive 30 to a partially inserted position.
- the control rod 20 is then raised to its fully inserted position, and two fuel assemblies 26 are installed in the positions not occupied by the blade guide 49.
- the blade guide 49 is then removed, and two more fuel assemblies 26 are installed in the positions from which the blade guide 49 was removed.
- Control rod replacement and shuffling operations at BWRs using the conventional procedures and tools described above often require excessively long times to perform.
- a wide variation in the time required (e.g., from 2 to 10 hours per control rod) and frequent long delays for serious problems (e.g., jammed fuel supports or inoperable tools) are common.
- a multi-lift tool apparatus for moving control rod assemblies in a nuclear reactor, the multi-lift tool apparatus comprising: a frame having an upper end and a lower end; a control rod grapple supported by the frame for engaging a lifting handle of a control rod; and a fuel support piece grapple secured to the lower end of the frame for engaging and lifting a fuel support piece together with the control rod.
- the control rod grapple is movable along a length of the frame for raising and lowering the control rod relative to the frame.
- a blade guide grapple is secured to the upper end of the frame for engaging and lifting a blade guide together with the fuel support piece and the control rod.
- An unlatching grapple is supported by the frame for engaging and lifting an unlatching handle of the control rod.
- the unlatching grapple is movable along a length of a lower portion of the frame for raising the unlatching handle of the control rod relative to the frame of the tool.
- the fuel support piece grapple comprises first and second tapered members for inserting into respective first and second holes of the fuel support piece.
- a lift cable is connected to the control rod grapple and extends upwardly from the frame of the tool to a hoist.
- the lift cable is movable relative to the frame to move the control rod grapple along a length of the frame.
- a pair of sheaves are mounted near the upper end of the frame for guiding the lift cable to extend upwardly from the tool frame along a central longitudinal axis of the frame.
- a first actuator is provided for selectively moving the control rod grapple into engagement with the lifting handle of the control rod.
- a plurality of second actuators are provided for selectively moving at least one latch of the fuel support piece grapple into engagement with the fuel support piece.
- a third actuator is provided for selectively moving the unlatching grapple into engagement with the unlatching handle, and a fourth actuator is provided for moving the unlatching grapple along a length of a lower portion of the frame for raising the unlatching handle of the control rod relative to the tool frame.
- a fifth actuator is provided for selectively moving the blade guide grapple into engagement with a handle of the blade guide.
- a method of moving a control rod assembly in a nuclear reactor comprising the steps of: lowering a lift tool into a control cell until a lower end of the lift tool is engaged with a fuel support piece; moving a control rod grapple supported by the lift tool into engagement with a lifting handle of a control rod; moving a fuel support piece grapple supported at a lower end of the lift tool into engagement with the fuel support piece; and raising the lift tool out of the control cell along with the control rod and the fuel support piece engaged with the lift tool, whereby the control rod and the fuel support piece are lifted out of the control cell together.
- a blade guide is inserted into the two open spaces left by the two removed fuel assemblies, and the two remaining diagonally opposed fuel assemblies are removed from the control cell.
- a blade guide grapple supported by the tool is then moved into engagement with the blade guide.
- the blade guide is then raised out of the control cell along with the lift tool, control rod, and fuel support piece.
- the method further comprises the steps of moving an unlatching grapple supported on a lower end of the lift tool into engagement with an unlatching handle of the control rod, and raising the unlatching grapple along with the unlatching handle relative to the frame of the lift tool to unlatch the control rod from the control rod drive.
- the control rod grapple is movable along a length of the frame of the lift tool to selectively raise and lower the control rod within the control cell relative to the fuel support piece.
- FIG. 1 is a perspective view of a conventional control rod for a boiling water nuclear reactor (BWR).
- BWR boiling water nuclear reactor
- FIG. 2a is a perspective view of a conventional control cell structure.
- FIGS. 2b and 2c are detail views of portions of the control cell structure shown in FIG. 2a.
- FIG. 3 is a cross-sectional view of a lower portion of a conventional control cell structure.
- FIGS. 4a and 4b are plan and elevation views, respectively, of conventional lifting equipment for replacing and shuffling control rods in a BWR.
- FIG. 5 is a schematic view of some of the moves required to replace control rods in a BWR using conventional tools.
- FIG. 6 is an elevation view of a multi-lift tool for shuffling and replacing control rods according to the present invention.
- FIG. 7 is a schematic elevation view of the multi-lift tool according to the present invention.
- FIG. 8 is a cross-sectional plan view taken near the top of the multi-lift tool of the present invention.
- FIG. 9 is a detail side view of a top portion of the multi-lift tool as viewed generally along line A--A in FIG. 8.
- FIG. 10 is a cross-sectional plan view taken near the bottom of the multi-lift tool of the present invention.
- FIG. 11 is a detail side view of a bottom portion of the multi-lift tool as viewed generally along line B--B in FIG. 10.
- FIGS. 12a and 12b are a plan view and side view, respectively, of an in-vessel storage station according to the present invention for storing two control rod blades and one fuel support piece.
- FIG. 13 is a schematic view of the moves required to replace control rods in a BWR using the multi-lift tool according to the present invention.
- the multi-lift tool 100 is designed to save valuable outage time in a BWR by combining several lifts into one during control rod exchange or shuffle operations. This is accomplished with a single tool which combines existing technologies to lift the fuel support piece 25, the blade guide 49, and the control rod 20 all at once.
- the multi-lift tool 100 of the present invention is used to exchange a control rod 20, the fuel support piece 25 and the blade guide 49 remain on the tool 100.
- the fuel support piece 25 forms the lower member of the tool frame as the control rod 20 is lifted from the guide tube 24.
- the blade guide 49 centers the whole lift and prevents hang-ups.
- the multi-lift tool 100 reinsertion of the fuel support piece 25, the blade guide 49, and the control rod 20 is accomplished with a single operation.
- the multi-lift tool 100 also functions to unlatch the control rod 20 from the control rod drive 30 before lifting the control rod 20 from the guide tube 24.
- the multi-lift tool 100 comprises a frame 101 made of square electropolished stainless steel tubes 101a, 101b.
- the tubes 101a, 101b are connected at the top by a bolted structure 101c which houses a blade guide grapple hook 102 with its operating cylinder 103.
- the tool 100 also includes sheaves or rollers 104 which transfer the lift cable 105 from an off-center control rod grapple 106 through the top of the tool 100 at a point generally along the central longitudinal axis of the tool 100.
- the bottom of the tubes 101a, 101b of the frame 101 connect to a fuel support piece grapple 107.
- a control rod lifter 108 in the form of a small trolley is provided which travels the length of the tubes 101a, 101b of the frame 101 on one side of the tool 100.
- the control rod lifter 108 supports the control rod grapple 106 and is operable to lower the control rod 20 into its cell for latching the control rod 20 to the control rod drive 30 at the bottom of the cell.
- the control rod lifter 108 can also lower the control rod 20 into a storage or transfer container.
- the control rod lifter 108 is connected directly to the lift cable 105 and is movable on cam rollers 108a along the length of the frame 101 by raising and lowering the lift cable 105.
- a lowered position of the control rod lifter 108 is shown in dashed lines in FIG. 7.
- the control rod grapple 106 is operated by a cylinder 109 to selectively engage and disengage with the control rod lifting handle 52.
- a bypass arrangement 105a is connected to the lift cable 105 above the tool 100 for guiding pressure lines 109a leading to the cylinder 109 around the sheaves 104.
- An unlatching handle grapple 110 is provided at the lower end of the multi-lift tool 100 just above the fuel support piece grapple 107.
- the unlatching handle grapple 110 is operated by two cylinders 111 and 112.
- the first cylinder 111 positions a D-ring finger 110a into selective engagement with the unlatching handle 53 on the control rod 20.
- the second cylinder 112 provides a lifting force for disengaging the unlatching handle 53.
- the fuel support piece 25 is grappled at the lower end of the tool 100 by the fuel support piece grapple 107.
- the grapple 107 comprises two cylindrical members 113 having tapered lower ends. Each cylindrical member 113 has three latches 114 which are operated by a respective cylinder 115 to move into locking engagement with the fuel support piece 25.
- the cylinders 115 like the other cylinders 103, 109, 111, 112 of the tool 100, cannot be activated while there is a load on the support device.
- the weight of the total lift according to the present invention is preferably under 1,000 pounds, which is within the lift capacity of the conventional hoists 46a, 46b, 46c provided for exchanging and shuffling the control rods 20 in a BWR. Only the weight of the control rod 20 is on the hoist during unlatching (i.e., when lifting the unlatching handle 53).
- the multi-lift tool 100 itself weighs approximately 400 pounds.
- FIGS. 12a and 12b An in-vessel storage station 200 according to the present invention is shown in FIGS. 12a and 12b for storing two control rods 20 and one fuel support piece 25.
- the storage station 200 comprises a frame 201 which hangs from the reactor flange and is retained by hooks which go around the studs on the reactor vessel.
- the storage station 200 is easily lowered into position with a cable which can be attached to the handrail for easy retrieval during removal. Alternate locations outside the reactor can be arranged according to individual plant preferences.
- the top of the storage station 200 has three openings 202 which simulate the core support plate openings.
- the lower end has two cups 203 which can receive the lower end of the control rods 20.
- the storage station 200 is constructed of electropolished stainless steel which is welded or bolted together for ease of decontamination and movement.
- a plurality of pads 204 made of delrin or other suitable material interface with the reactor.
- two diagonally opposed fuel assemblies 26 are removed one at a time from the control cell with the main grapple and transported to storage in the spent fuel pool, to an in-vessel storage rack, or to another core location as part of a fuel shuffle.
- a blade guide 49 is transported on the main grapple from a storage location and inserted into the open holes of the control cell.
- the remaining two fuel assemblies 26 are then removed one at a time from the cell with the main grapple and are stored in the pool or another location. The operation up to this point is the same as in the conventional procedures.
- the multi-lift tool 100 is then placed into the cell with the control rod 20 fully inserted.
- the cylinders on the multi-lift tool 100 are actuated to grapple the fuel support piece 25, the blade guide 49, and the control rod 20.
- Video cameras are inserted into the open holes of the control cell (i.e., the holes without the blade guide 49 positioned therein) to verify the latching operations.
- the multi-lift tool 100 is then actuated to grapple the unlatching handle and unlatch the control rod 20 from the control rod drive 30 with the control room giving a continuous withdraw signal.
- the control rod drive 30 is then withdrawn to the overtravel position.
- This storage position can include, for example, the in-vessel storage station 200 or a suitable rack in the spent fuel pool.
- the old control rod 20 and fuel support piece 25 are then discharged, and the multi-lift tool 100 is moved to another part of the storage station and attached to a replacement control rod 20 and fuel support piece 25 for the cell.
- the multi-lift tool 100 then carries the assembly comprising the new control rod, the original blade guide 49, and the new fuel support piece 25 to a position above the control cell. This is represented by step (2) in FIG. 13.
- the multi-lift tool 100 then places the new assembly into the control cell and lowers the control rod 20, thereby seating the fuel support piece 25, the blade guide 49, and the control rod 20 in the control cell.
- the placement and alignment of the fuel support piece 25 onto the anti-rotation pin is verified with a camera in one of the two open holes of the control cell.
- the multi-lift tool 100 is then withdrawn.
- the control rod grapple 106 has a retaining barb 116.
- the operating cylinder 109 does not have the power to overcome the weight of the control rod 20 against the control rod grapple 106 with the retaining barb 116 at its outer edge.
- the lift cable 105 is attached directly to the control rod grapple 106 so that its function cannot be bypassed when the tool 100 is moved under load. Due to the sliding trolley arrangement, the control rod 20 cannot be lowered out of the lift assembly without the bottom end of the assembly being supported.
- the blade guide grapple 102 also has a barb 117 to retain the handle of the blade guide 49. While the fuel support piece 25 is attached, the blade guide grapple 102 is redundant since the fuel support piece 25 prevents the blade guide 49 from being lowered.
- the blade guide grapple 102 is barbed to prevent the blade guide 49 from moving and is hinged in a way which would support the blade guide 49 if the power is shut off.
- the multi-lift tool 100 lifts the blade guide 49 with the control rod 20. Since this assembly is never completely below the grid 51, there is a greatly reduced chance of any type of hang-up either going down through the grid 51 or in the removal process. No hoist overloads are necessary for this reason.
- the tubes 101a, 101b of the frame 101 function as a guide to locate the tool 100 centrally in the grid opening.
- the unlatching handle grapple 110 can be left in its unlatched position for added lifting safety during transport if desired.
- the fuel support piece 25 is grappled by the two bullet nosed grapples 107.
- Each bullet nose 113 has three latches 114 which cannot be actuated when the weight of the fuel support piece 25 is on them. This is a double redundant system since the latches 114 must move up in order to unlatch and there are two direct support paths (i.e., two bullet noses 113), each with three latches 114.
- the blades of the control rod 20 are guided by the blade guide 49 which is, at that time, integral with and supported by the tool 100.
- the blade guide 49 which is, at that time, integral with and supported by the tool 100.
- Corrosion resistance is enhanced by the use of stainless steel parts. Where possible these parts are electropolished for ease of decontamination. Aluminum parts can be used for certain components, but must receive a hard anodized coating to resist corrosion.
- Loose parts are controlled predominantly by lock wiring since most of the construction of the tool 100 embodies bolting methods.
- a locking agent can be used to prevent loosening of parts, particularly if the part is not subjected to significant torque.
- Bent tab keepers can also be used to prevent loosening of parts on the tool 100.
- the reactor water will provide sufficient lubrication to permit smooth operation of the moving parts of the tool 100.
- the cylinders 103, 109, 111, 112, and 115 of the tool 100 are preferably air cylinders which will perform optimally using 90-120 psig air supplies.
- the end of the lift cable 105 is adaptable for use with any desired hoisting device positioned over the BWR.
- the core configuration for support of the tool 100 does not need to be changed after initial removal of fuel and installation of the blade guide 49.
- the tool 100 removes the control rod 20, the blade guide 49, and the fuel support piece 25 together.
- the control rod drive 30 is retracted during the unlatching of the control rod 20 within the tool 100.
- the installation of the control rod 20 using the tool 100 takes place in the same manner, except the control rod 20 is lowered to the control rod drive 30.
- the whole tool 100 is inserted into the control cell guided by the existing blade guide 49 and the control rod 20. Once installed, the top of the tool 100 is still above the grid 51 allowing ease of removal guided by the blade guide 49. The bottom of the assembly of the tool 100, the blade guide 49, and the control rod 20 is stiffened by the fuel support piece 25.
- Each of the operation cylinders 115 for the fuel support piece grapple 107 has a double ended shaft which can be used to visually determine the position of the latches 114. If the latches 114 are not extended, the cylinders 115 will not stroke. Visual verification is possible through the two fuel positions which are not occupied by the blade guide 49.
- One cell is removed completely with the fuel support piece 25.
- the control rod 20 is then placed in an intermediate position such as a so-called gun barrel or in-vessel storage station 200 (FIGS. 12a, 12b).
- a new control rod 20 is retrieved from the same intermediate position, and the assembly is returned to the original cell as a whole for relatching.
- the fuel support piece 25 may be released onto the same intermediate position in unusual situations, such as during replacement of the fuel support piece 25.
- the tool 100 is capable of placing the control rod 20 into the gun barrel, but not with the fuel support piece 25 on the tool.
- the fuel support piece 25 must be set down on the in-vessel storage station 200 or another gun barrel before the control rod 20 can be lowered fully. Modification of the gun barrel by cutting down the height by 20 inches or adding a spool support piece inside the barrel are alternate solutions.
- the multi-lift tool 100 solves many of the problems with conventional tools for exchanging and shuffling control rods.
- the multi-lift tool 100 is not subject to the problem of jamming under the grid 51 because part of the tool 100 always remains above the grid 51.
- the blade guide 49 becomes an integral part of the tool 100 during the lift operation providing guidance in the horizontal and rotational directions at all times after the assembly enters the grid 51. Access for video cameras is possible through the two fuel locations not taken up by the blade guide 49.
- Slack cable is not an issue because the trolley 108 can be made to weigh the necessary amount to draw the lift cable 105 into the tool 100.
- the multi-lift tool 100 is suited to either of the hoists 47a, 47c available on the refuel bridge.
- the total weight of the tool 100 with the attached blade guide 49, control rod 20, and fuel support piece 25 is less than 1000 pounds. Therefore, the hoist used can be the one with the most accessibility for the user, thereby improving safety.
- the tool 100 can be designed to be used with any of the hoists 47a, 47b, 47c available on the refuel floor by making it usable with either a rigid pole system fitting or a threaded connection on the end of the lift cable.
- Rotational positioning of the fuel support piece 25 is controlled at the entrance to the grid 51. After this point, there is no possibility of the fuel support piece 25 rotating due to the presence of the blade guide 49 as part of the assembly. Engagement with the grid 51 is maintained throughout the lowering and raising of the assembly.
- the unlatching handle 53 is grappled by the unlatching handle grapple 110 using the two cylinders 111, 112.
- the cylinders 111, 112 are directly connected to the frame 101 which, in turn, is stiffened by the presence of the fuel support piece 25.
- the two cylinders 111, 112 are operated to provide easy access and unlatching of the control rod 20.
- the unlatching operations are accomplished with an unlatching handle grapple 110 designed for maximum vertical flexibility. The vertical height depends on the vertical cylinder 112 operating the unlatching handle grapple 110.
- the unlatching handle grapple 110 is designed to sustain the weight of the control rod 20, however this is not the primary method of supporting the control rod 20.
- the main control rod grapple 106 is at the top of the multi-lift tool 100. When both grapples 106 and 110 are latched there is redundancy in the lift.
- the unlatching handle grapple 110 can be eliminated from the lift sequence if desired due to the unique application of the trolley lift.
- the blade guide 49 becomes an integral part of the positioning of the control rod 20 within the tool 100 and provides the necessary guidance.
- Two fuel positions are essentially open in the control cell to allow camera access to the entire length of the tool 100. This same access provides clearance to insert a conventional rigid pole system for remedial action should that ever be required.
- the multi-lift tool 100 has no unguided air hoses below the grid 51 because a portion of the tool 100 is always above the grid 51. Only the air hose cluster, the lift cable 105, and a guide rope (not shown) extend to the surface. The guide rope is used to counter rotation of the tool 100 before it enters the grid 51. The rotation is usually caused by the lift cable 105 unwinding as it is played out from the hoist.
- the multi-lift tool 100 has the potential of changing a two hour exchange of the control rod 20 into a half hour exercise without hangups. This adds a great deal of consistency to the operation. Since the unlatching of the control rod 20 takes place with the control rod 20 in the up position, some communication time can be saved with the control rod drive operation. Unlatching is allowed with the control rod 20 inserted because the blade guide 49 travels with and becomes part of the multi-lift tool 100.
- Table 1 shows a comparison of the typical times required for the control rod replacement procedures using the conventional tools and using the improved multi-lift tool 100 of the present invention.
- the cost of the new multi-lift tool 100 can be easily justified in just one outage.
- a control rod shuffle can be accomplished very quickly changing a cell operation from 4 hours to around 1 hour due to the elimination of steps.
- the use of two multi-lift tools according to the present invention could further enhance this operation or the exchange noted above.
Abstract
Description
TABLE 1 ______________________________________ Time Comparison for Blade Replacement Operations Current Time Multi-Lift Operation (min) Time (min) ______________________________________ a. BG cell to hanging 5 b. FSP cell to hanging 13 c. CR cell topool rack 36 15 d. CR pool rack tocell 27 15 e. FSP hanging to cell 20 f. BG hanging tocell 8 Total Time 109 30 ______________________________________
______________________________________ 10 Blades Replaced $104,000Savings 20 Blades Replaced $208,000 Savings ______________________________________
Claims (17)
Priority Applications (1)
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US08/871,031 US6047037A (en) | 1997-05-19 | 1997-05-19 | Multi-lift tool and method for moving control rods in a nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
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US08/871,031 US6047037A (en) | 1997-05-19 | 1997-05-19 | Multi-lift tool and method for moving control rods in a nuclear reactor |
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US6047037A true US6047037A (en) | 2000-04-04 |
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US08/871,031 Expired - Lifetime US6047037A (en) | 1997-05-19 | 1997-05-19 | Multi-lift tool and method for moving control rods in a nuclear reactor |
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Cited By (14)
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US6295329B1 (en) * | 1998-04-27 | 2001-09-25 | Kabushiki Kaisha Toshiba | Apparatus and method for handling reactor-internal equipments |
US6501813B1 (en) * | 1997-06-11 | 2002-12-31 | Kabushiki Kaisha Toshiba | Control rod/fuel support grapple |
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US9793013B2 (en) | 2009-11-06 | 2017-10-17 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
US20110110478A1 (en) * | 2009-11-06 | 2011-05-12 | Searete Llc, A Limited Liability Corporation Of The State Of Delaware | Systems and methods for controlling reactivity in a nuclear fission reactor |
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US20150148962A1 (en) * | 2013-11-25 | 2015-05-28 | Liebherr-Werk Nenzing Gmbh | Method for controlling the fill volume of a grapple |
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